A facility for the irradiation of a section of patients' explanted liver and lung was constructed at RA-3 reactor, Comisión Nacional de Energía Atómica, Argentina. The facility, located in the thermal column, is characterized by the possibility to insert and extract samples without the need to shutdown the reactor. In order to reach the best levels of security and efficacy of the treatment, it is necessary to perform an accurate dosimetry. The possibility to simulate neutron flux and absorbed dose in the explanted organs, together with the experimental dosimetry, allows setting more precise and effective treatment plans. To this end, a computational model of the entire reactor was set-up, and the simulations were validated with the experimental measurements performed in the facility. © 2011 Elsevier Ltd.
Documento: | Artículo |
Título: | Simulation of the neutron flux in the irradiation facility at RA-3 reactor |
Autor: | Bortolussi, S.; Pinto, J.M.; Thorp, S.I.; Farias, R.O.; Soto, M.S.; Sztejnberg, M.; Pozzi, E.C.C.; Gonzalez, S.J.; Gadan, M.A.; Bellino, A.N.; Quintana, J.; Altieri, S.; Miller, M. |
Filiación: | Department of Nuclear and Theoretical Physics, University of Pavia, Via Bassi 6 27100, Pavia, Italy National Institute of Nuclear Physics (INFN), Section of Pavia, Via Bassi 6 27100, Pavia, Italy Department of Instrumentations and Control, Comisión Nacional de Energía Atómica (CNEA), Presbítero Luis González y Aragon 15 (B1802AYA), Buenos Aires, Argentina Department of Research and Production Reactors, Comisión Nacional de Energía Atómica (CNEA), Av. del Libertador 8250 (1429), Buenos Aires, Argentina Department of Radiobiology, Comisión Nacional de Energía Atómica (CNEA), Av. del Libertador 8250 (1429), Buenos Aires, Argentina CONICET, Avda. Rivadavia 1917, (1033) C.A.B.A., Argentina FCEyN, Universidad de Buenos Aires (1428), Cdad. Universitaria. C.A.B.A., Argentina |
Palabras clave: | BNCT; Irradiation facility simulation; Neutron dosimetry; Absorbed dose; Argentina; BNCT; Computational model; Experimental measurements; Irradiation facilities; Irradiation facility simulation; Neutron dosimetry; Thermal column; Treatment plans; Computer simulation; Dosimetry; Extraction; Mica; Neutron beams; Neutron flux; Plant shutdowns; Neutron irradiation; article; controlled study; mathematical analysis; Monte Carlo method; neutron capture therapy; neutron dosimetry; neutron radiation; phantom; priority journal; radiation dose; reactor; simulation; treatment planning |
Año: | 2011 |
Volumen: | 69 |
Número: | 12 |
Página de inicio: | 1924 |
Página de fin: | 1927 |
DOI: | http://dx.doi.org/10.1016/j.apradiso.2011.03.034 |
Título revista: | Applied Radiation and Isotopes |
Título revista abreviado: | Appl. Radiat. Isot. |
ISSN: | 09698043 |
CODEN: | ARISE |
Registro: | https://bibliotecadigital.exactas.uba.ar/collection/paper/document/paper_09698043_v69_n12_p1924_Bortolussi |